LFR在正常运行和堵塞条件下的IWF特性研究

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-09-23 DOI:10.1016/j.nucengdes.2025.114481

Di Wu , Minyang Gui , Jie Cheng , Jianjun Wang

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引用次数: 0

摘要

铅基快堆（LFR）工程应用的前提是保证堆的安全可靠运行；因此，对LFR的热安全特性进行研究至关重要。利用开发的子信道代码，分析了LFR在正常运行和阻塞条件下的包层流特性。用现有实验数据对所开发的子信道码进行了验证，误差在±10℃以内，编码精度可接受。在此基础上，研究了IWF、装配流量和整个杆束功率对热工参数的影响。此外，还考虑了单个组件热参数变化的影响，包括三个杆束中只有一个的流量是原来的50%，整个加热功率是原来的20%的情况。最后，对局部水流堵塞事故进行了分析，并对不同的堵塞子通道和堵塞区域进行了调查。研究结果可为LFR的热分析和优化设计提供参考。

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Research on the IWF characteristics of LFR under normal operation and blockage conditions

The prerequisite for the engineering application of lead-based fast reactors (LFR) is to ensure the safe and reliable operation of the reactor; thus, it is crucial to conduct research on the thermal safety characteristics of LFR. In this study, the inter-wrapper flow (IWF) characteristics of LFR under normal operation and blockage conditions were analyzed with the developed sub-channel code. The developed sub-channel code was verified with the existing experimental data, and the deviation is within ± 10°C, which means the accuracy of the code is acceptable. Furthermore, the influence of IWF, assembly flow rate, and the power of the whole rod bundle on the thermal–hydraulic parameters was studied. The impact of changes in the thermal parameters of individual assemblies was considered as well, including the condition where only one of three rod bundles’ flow rate is 50 % of the original, and the whole heating power is 20 % of the original. Finally, the local flow blockage accidents were analyzed, and the different blockage sub-channels and blockage areas were investigated. The research could provide a reference for the thermal analysis and optimization design of LFR.

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.